| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Irradiation Testing: Facilities, Capabilities, and Experimental Designs
|
| Presentation Title |
Post-irradiation Examination of AGR-5/6/7 TRISO Fuel with Micro X-ray Computed Tomography |
| Author(s) |
William Chuirazzi, Rahul Reddy Kancharla, John Stempien, Swapnil Morankar |
| On-Site Speaker (Planned) |
Swapnil Morankar |
| Abstract Scope |
Tristructral isotropic (TRISO) coated fuel particles are a fuel form under study for commercial qualification to power certain next-generation nuclear reactor designs. Nondestructive micro X-ray Computed Tomography (XCT) examinations have recently been used to complement traditional destructive analyses. While XCT results of AGR-2, AGR-3/4, and initial results on a small sample of AGR-5/6/7 particles have previously been reported, this work focuses on a more comprehensive examination of a larger sample of irradiated AGR-5/6/7 particles at Idaho National Laboratory’s Irradiated Materials Characterization Laboratory (IMCL). These results enable analysis of post-irradiation TRISO particle properties such as layer thicknesses as well as observations of defects and buffer layer delaminations. This presentation also includes application of lessons learned from previous XCT examinations to improve and expedite data collection. Finally, the impact of post-irradiation examination XCT on destructive analysis as well as XCT data's usefulness in observing fuel performance under irradiation conditions is discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |